Uses of PRA in nuclear reactor regulation
Description
For the past five years, more than ten probabilistic risk assessment (PRA) studies were conducted by the owners of nuclear utilities and were submitted for the review of US Nuclear Regulatory Commission staff. These PRA studies were reviewed under various types of regulatory activities depending on the nature of plant licensing stage. The reviews of these PRAs provided very valuable uses to both the staff and the licensees on safety matters of the plant operation. The licensees developed perspectives using PRA models on the safety profiles of their plants. These PRA perspectives influenced licensees' major decisions to implement improvements to plant design and operating and emergency procedures to reduce and/or eliminate the plant's vulnerability to core damage accidents. The staff's review of these PRAs particularly emphasized the dominant accident sequences. The resulting findings led to the identification of dominant risk contributors, critical areas of plant locations, mechanisms leading to potential early containment failures, and instances of noncompliances of staff's deterministic criteria. Specific examples include single failure criterion and separation requirements to assess the need for any additional measures to further improve the safety of the plant. Some of these PRAs were reviewed under regulatory activities other than safety review such as environmental review, final design review, and licensing hearings. Most importantly, the risk profiles of generic PRAs will continue to be used in reviewing and evaluating unresolved safety issues and other generic issues. The major regulatory uses of PRAs, a summary of full scope PRA review, a summary of plant improvements as a result of PRA reviews, and the future role of PRA reviews are presented
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fourteenth water reactor safety information meeting. Volume 1. Plenary session, severe accident sequence analysis, risk analysis/PRA applications, reference plant risk analysis - NUREG-1150, innovative concepts for increased safety of advanced power reactors
- Journal Page Range
- p. 125-138.
- Report number
- NUREG/CP--0082-Vol.1
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19002065
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; PROBABILITY; PWR TYPE REACTORS; REACTOR LICENSING; REACTOR SAFETY; REGULATIONS; RISK ASSESSMENT; US NRC
- Descriptors DEC
- ENRICHED URANIUM REACTORS; LAW; LICENSING; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS